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Development of a robust, accurate and efficient coupling between PLEIADES/ALCYONE 2.1 fuel performance code and the OpenCalphad thermo-chemical solver

Nuclear engineering and design, 2020-12, Vol.369, p.110818, Article 110818

2020

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Phase-field modeling with the TAF-ID of incipient melting and oxygen transport in nuclear fuel during power transients

Journal of nuclear materials, 2021-12, Vol.556, p.153173, Article 153173

2021

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Corrigendum to “Simulation of reactivity initiated accident thermal transients on nuclear fuels with laser remote heating”

Journal of nuclear materials, 2021-12, Vol.556, p.153154, Article 153154

2021

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Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests

Journal of nuclear materials, 2022-04, Vol.561, p.153527, Article 153527

2022

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Simulation of reactivity initiated accident thermal transients on nuclear fuels with laser remote heating

Journal of nuclear materials, 2020-03, Vol.530 (13), p.151944, Article 151944

2020

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Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents

Journal of nuclear materials, 2022-03, Vol.560, p.153429, Article 153429

2022

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2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE

Nuclear technology, 2024-02, Vol.210 (2), p.269-284

2024

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Study of the hardness and Young's modulus at the fuel-cladding interface of a high-burnup PWR fuel rod by nanoindentation measurements

Journal of nuclear materials, 2022-03, Vol.560, p.153511, Article 153511

2022

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3D thermo-chemical–mechanical simulation of power ramps with ALCYONE fuel code

Journal of nuclear materials, 2014-09, Vol.452 (1-3), p.578-594

2014

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3D simulation of a power ramp including fuel thermochemistry and oxygen thermodiffusion

Journal of nuclear materials, 2019-06, Vol.519, p.104-120

2019

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Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE

Nuclear technology, 2024-02, Vol.210 (2), p.285-307

2024

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P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments

Nuclear technology, 2024-02, Vol.210 (2), p.189-215

2024

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Fungal fragments and undocumented conidia function as new aeroallergen sources

Journal of Allergy and Clinical Immunology, 2005-05, Vol.115 (5), p.1043-1048

2005

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Determination of the Gas Plenum Temperature of the P2M Instrumented Fuel Rodlets on the Basis of a Thermal-Hydraulic Study of the Belgian Reactor 2 Pressurized Water Capsule

Nuclear technology, 2024-02, Vol.210 (2), p.354-377

2024

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3D fuel cracking modelling in pellet cladding mechanical interaction

Engineering fracture mechanics, 2008-07, Vol.75 (11), p.3581-3598

2008

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Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment

Nuclear technology, 2013-05, Vol.182 (2), p.124-137

2013

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Experimental evidence of oxygen thermo-migration in PWR UO2 fuels during power ramps using in-situ oxido-reduction indicators

Journal of nuclear materials, 2016-11, Vol.480, p.32-39

2016

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Experimental study of gas diffusion in cement paste

Cement and concrete research, 2007-04, Vol.37 (4), p.579-588

2007

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Long-term performance of cement paste during combined calcium leaching–sulfate attack: kinetics and size effect

Cement and concrete research, 2006, Vol.36 (1), p.137-143

2006

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Power ramped cladding stresses and strains in 3D simulations with burnup-dependent pellet–clad friction

Nuclear engineering and design, 2012, Vol.242, p.164-181

2012

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The reduction of rhinitis symptoms by nasal filters during natural exposure to ragweed and grass pollen

Allergy (Copenhagen), 2005-04, Vol.60 (4), p.529-532

2005

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Stratigraphic evidence for an early collision between northwest India and Asia

Nature (London), 1995-01, Vol.373 (6509), p.55-58

1995

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Rehydration and microstructure of cement paste after heating at temperatures up to 300 °C

Cement and concrete research, 2003-07, Vol.33 (7), p.1047-1056

2003

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A new phenomenological criterion for pellet–cladding interaction rupture

Nuclear engineering and design, 2008-07, Vol.238 (7), p.1612-1628

2008

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Experimental and numerical study of fracture mechanisms in UO2 nuclear fuel

Engineering failure analysis, 2015-01, Vol.47, p.299-311

2015

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Development of a robust, accurate and efficient coupling between PLEIADES/ALCYONE 2.1 fuel performance code and the OpenCalphad thermo-chemical solver

Phase-field modeling with the TAF-ID of incipient melting and oxygen transport in nuclear fuel during power transients

Corrigendum to “Simulation of reactivity initiated accident thermal transients on nuclear fuels with laser remote heating”

Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests

Simulation of reactivity initiated accident thermal transients on nuclear fuels with laser remote heating

Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents

2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE

Study of the hardness and Young's modulus at the fuel-cladding interface of a high-burnup PWR fuel rod by nanoindentation measurements

3D thermo-chemical–mechanical simulation of power ramps with ALCYONE fuel code

3D simulation of a power ramp including fuel thermochemistry and oxygen thermodiffusion

Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE

P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments

Fungal fragments and undocumented conidia function as new aeroallergen sources

Determination of the Gas Plenum Temperature of the P2M Instrumented Fuel Rodlets on the Basis of a Thermal-Hydraulic Study of the Belgian Reactor 2 Pressurized Water Capsule

3D fuel cracking modelling in pellet cladding mechanical interaction

Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment

Experimental evidence of oxygen thermo-migration in PWR UO2 fuels during power ramps using in-situ oxido-reduction indicators

Experimental study of gas diffusion in cement paste

Long-term performance of cement paste during combined calcium leaching–sulfate attack: kinetics and size effect

Power ramped cladding stresses and strains in 3D simulations with burnup-dependent pellet–clad friction

The reduction of rhinitis symptoms by nasal filters during natural exposure to ragweed and grass pollen

Stratigraphic evidence for an early collision between northwest India and Asia

Rehydration and microstructure of cement paste after heating at temperatures up to 300 °C

A new phenomenological criterion for pellet–cladding interaction rupture

Experimental and numerical study of fracture mechanisms in UO2 nuclear fuel

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